ENTRY 22103 20110207 22262210300000001 SUBENT 22103001 20110207 22262210300100001 BIB 14 61 2210300100002 REFERENCE (J,ANE,15,(7),363,198807) 2210300100003 TITLE -Measurement of the cross section for the reaction 2210300100004 Nb-93(n,inl)Nb-93-m at 2.8 MeV. 2210300100005 AUTHOR (M.Wagner,G.Winkler,H.Vonach,G.Petoe) 2210300100006 INSTITUTE (3HUNKOS) G.Petoe. 2210300100007 (2AUSIRK) M.Wagner, G.Winkler, H.Vonach. 2210300100008 FACILITY (CCW,3HUNKOS) The neutron generator of the Institute 2210300100009 of Experimental Physics at Debrecen, was used to 2210300100010 produce a 250 micro-Amps analysed beam of 220 +/- 5 keV2210300100011 deuterons. 2210300100012 INC-SOURCE (D-D) An air-jet cooled Ti-D target thicker than the 2210300100013 range of the deuterons with a 0.33 mm thick Mo backing2210300100014 was employed in a low-mass beam line construction. 2210300100015 METHOD (ACTIV) A fission chamber with niobium and monitor 2210300100016 foils mounted inside and outside the chamber was 2210300100017 placed at 0 degrees relative to the deuterium beam. 2210300100018 DETECTOR (SOLST) A Si(Li) X-ray detector, 25 mm in diameter and 2210300100019 5 mm thick with a 0.0125 mm beryllium window, giving 2210300100020 a resolution of 400 eV at 17 keV, was used for the 2210300100021 measurement of the niobium K-shell X-radiation. The 2210300100022 absolute efficiency of the detector was determined by 2210300100023 means of a thin, point-like Nb-93m reference source. 2210300100024 (FISCH) A fission chamber, containing 168.2 +/- 2.5 2210300100025 micrograms of U-238, enriched to 99.98%, in 2210300100026 form of the compound UF4, was used. The chamber was 2210300100027 operated with a voltage gradient of 600 V/cm and a 2210300100028 continuous gas flow of pure argon counting gas. The 2210300100029 mass of U-238 was determined by comparing with the 2210300100030 activity in an aluminium foil after irradiation with 2210300100031 14.8 MeV neutrons, using the ratio of the well-known 2210300100032 cross sections for 13-Al-27(n,a)11-Na-24 and 2210300100033 92-U-238(n,f). The cross sections used were 112.10 mb 2210300100034 +/- 0.6% and 1184.4 mb +/- 1.2%, respectively. 2210300100035 MONITOR (92-U-238(N,F),,SIG) The neutron fluence determined 2210300100036 with the 10 mm diameter fissionable material was 2210300100037 interrelated to the 20 mm diameter niobium foils by 2210300100038 also irradiating nickel foils with these two dia- 2210300100039 meters. 2210300100040 SAMPLE .Niobium foils, 20 mm diameter and with a mass of 2210300100041 364.24 grams, positioned 1 cm from the neutron source,2210300100042 were used. The foils were irradiated for 210 hours, 2210300100043 resulting in a total neutron fluence of 9.0000e+12 2210300100044 n/cm2. Nickel foils were used for size normalisation. 2210300100045 A tantalum foil, 20 mm in diameter and 0.1 mm thick 2210300100046 was used for determining the background from tantalum 2210300100047 impurities in the niobium samples. 2210300100048 CORRECTION .Corrections were applied for self-absorption in the 2210300100049 foils and for the effects of the extension of the 2210300100050 source. Further, the data were corrected for fluore- 2210300100051 scence caused by Ta impurities in the Nb samples, for 2210300100052 elastic neutron scattering and for background. 2210300100053 ERR-ANALYS (DATA-ERR) The errors are composed of contributions 2210300100054 from the measurement of the Nb-93 activity and from 2210300100055 fluence related measurements. 2210300100056 STATUS (TABLE) .Data taken from main ref. 2210300100057 (SPSDD,30925001) Entry deleted. Duplication with 30925 2210300100058 HISTORY (19881102C) N.O. 2210300100059 (19881216E) 2210300100060 (20110207D) SD: Entry deleted. Duplication with 30925 2210300100061 Updated to new date formats,lower case. 2210300100062 corrected according to last EXFOR rules and Dict. 2210300100063 ENDBIB 61 0 2210300100064 COMMON 5 3 2210300100065 EN EN-ERR EN-RSL MONIT MONIT-ERR 2210300100066 MEV MEV MEV MB PER-CENT 2210300100067 2.8300E+00 4.0000E-02 1.2800E-01 5.2320E+02 1.0000E+00 2210300100068 ENDCOMMON 3 0 2210300100069 ENDSUBENT 68 0 2210300199999 NOSUBENT 22103002 20110207 22262210300200001 ENDENTRY 2 0 2210399999999